Thermo-fluid dynamics and corrosion analysis of a self cooled lead lithium blanket for the HiPER reactor-Reference-Cited by-同舟云学术

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Thermo-fluid dynamics and corrosion analysis of a self cooled lead lithium blanket for the HiPER reactor

Published:2015-07-30 Issue:9 Volume:55 Page:093003
ISSN:0029-5515
Container-title:Nuclear Fusion
language:
Short-container-title:Nucl. Fusion

Author:

Juárez R.,Zanzi C.,Hernández J.,Sanz J.

Funder

HiPER Preparatory Phase Study European Commission-Grant Agreement

Spanish MINECO (Ministerio de Economia y Competitividad)

ETS Ingenieros Industriales-UNED

Programa de Actividades I+D de la Comunidad de Madrid

Publisher

IOP Publishing

Subject

Condensed Matter Physics,Nuclear and High Energy Physics

Link

http://stacks.iop.org/0029-5515/55/i=9/a=093003/pdf

Reference40 articles.

1. Dose rates evaluation of HiPER facility

2. Advances in neutronics and radiological protection of HiPER 4a

3. Waste Management Assessment of Candidate Materials for HiPER Reaction Chamber

4. Repetition rate target and fusion chamber systems for HiPER

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Future for inertial-fusion energy in Europe: a roadmap;High Power Laser Science and Engineering;2023

2. Limitations for tungsten as plasma facing material in the diverse scenarios of the European inertial confinement fusion facility HiPER: Current status and new approaches;Matter and Radiation at Extremes;2020-09-01

3. Modelling the thermomechanical behaviour of the tungsten first wall in HiPER laser fusion scenarios;Nuclear Fusion;2016-09-14

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